IR 05000482/1986025

Insp Rept 50-482/86-25 on 861006-10.No Violations or Deviations Noted.Major Areas Inspected:Licensee Radiation Protection Program Preplanning for Refueling Outage, Including Training & Qualification & ALARA

ML20215D498
Person / Time
Site:	Wolf Creek
Issue date:	11/21/1986
From:	Baer R, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20215D473	List: IR 05000482/1986025 ML20215D471
References
50-482-86-25, NUDOCS 8612160381
Download: ML20215D498 (6)

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APPENDIX

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U.S. NUCLEAR REGULATORY COMISSION

REGION IV

NRC Inspection Report: '50-482/86-25 License: NPF-42 Docket: 50-482 Licensee: Kansas Gas and Electric Company (KG&E)

P. O. Box 208 Wichita, Kansas 67201 9 Facility Name: ' Wolf Creek Generating Station (WCGS)

Inspection At: WCGS Site, Burlington, Kansas Inspection Conducted: October 6-10, 1986 Inspector:

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/4 '. E. Baer, Radiation Radiological Specialist, Protection Section Facilities Approved: ( [ k/ d B. Murray, Chief, Facilfties Radiological Date Protection Section i-Inspection Summary Inspection Conducted October 6-10, 1986 (Report 50-482/86-25)

Areas Inspected: Routine, unannounced inspection of the licensee's radiation protection program preplanning for the refueling outage including: advance planning and preparation, staffing, training and qualifications, ALARA, external exposure control and internal exposure contro Results: Within the areas inspected, no violations or deviations were

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-2-DETAILS

. Persons Contacted

[ KG&E

• G. D. Boyer, Deputy Plant Manager

• L. F. Breshears, Health Physics Supervisor

• M. Davis, Health Physics Supervisor G. D. Freund, Instrumentation and Control Group Supervisor C. J. Hoch, Quality Assurance (QA) Technologist J. M. Isom, Health Physics Supervisor J. A. Ives, Site Health Physicist

• M. Lindsay, Supervisor, Quality Systems R. L. Logston, Site Chemist G. A. McClelland, QA Lead Auditor T. S. Morrill, Chemistry Supervisor

• M. Nichols, Superintendent, Plant Support C. L. Palmer, Chemistry Supervisor

• J. Pendergrass, Licensing Engineer

• K. R. Peterson, Licensing Lead Engineer

• W. J. Rudolph, II, Manager, QA R. M. Stambaugh, QA Supervisor, Audits C. L. Taylor, Health Physics Supervisor

• M. G. Williams, Superintendent, Regulatory, Quality, and Administration Others

• D. Allen, Health Physics Consultant

• B. L. Bartlett, NRC Resident Inspector J. E. Cummins, NRC Senior Resident Inspector The NRC inspector also interviewed several other licensee employees and contractors including administrative, health physics, and chemistry personne * Denotes those individuals present during the exit interview on October 10, 198 . Licensee Action on Previously Identified Open Items (Closed) Open Item (482/8520-01): Gaseous Radwaste System Representative Sampling - This item involved the lack of verification that gaseous effluent samples were representative of the discharge volume. The licensee performed special test SPE CH-002, " Verification of Representative Sampling of the Waste Gas System," between September 25, and November 5, 1985, and demonstrated recirculation times necessary to obtain a representative sampling from the waste gas storage tank. This item is considered close ,

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(Closed),0 pen Item.(482/8520-02): Calibration of Process Radiation

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- Monitors - This item involved.the lack of a calibration for liquid and gaseous process radiation monitors with NBS traceable radioactive liquid and gaseous. sources. The licensee calibrated the 24 process radiation monitors with NBS traceable radioactive liquid'and gaseous sources between July and October 1985. This item is considered close (Closed) Open Item (482/8520-03): Calibration Procedures for Process and Effluent Monitors - This item involved the lack of calibration procedures for process and effluent monitors to require calibration on one point per-decade over the full range of the instrument. The licensee had issued

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. calibration procedures for all 42 safety and non-safety-related process

and effluent radioactivity monitors addressing one point per decade calibration over the full range of the instrument. This item is considered close . . Advance Planning and Preparations

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The NRC' inspector reviewed preparations for the.first refueling outag The licensee had not completed all facility changes at the time of this inspection. The licensee was completing the installation of a fence

.around sections of the~ reactor, fuel, radwaste, drum storage, and hot machine shop buildings, which will-allow the extension of the radiologically controlled area (RCA) outside these buildings into the fenced-off area. The licensee had constructed a pad outside the radwaste building, within the RCA, to facilitate one mobile respirator cleaning facility and two mobile self-contained laundry facilities. These facilities were in place at the conclusion of the inspectio The licensee had set up a secondary control point at the 2026-foot elevation to control personnel entering and leaving the reactor building via the personnel airlock. Three personnel frisking stations are set up outside the personnel. airlock and two personnel contamination monitors are located by the secondary control point. Two additional personnel contamination monitors had been installed at the normal control poin The licensee had developed procedure ADM 01-207, " Refueling Outage Health Physics Program," Revision 0, September 25, 1986, which designates outage responsibilities within the health physics department, changes for access control, exposure limits, radiation work permit (RWP) requirements, ALARA reviews, and waste handlin The NRC inspector reviewed the quantities of protective clothing, portable radiation monitoring instruments, respiratory protective devices, and dosimeters available to support the outage. The licensee appeared to have sufficient quantities of these items on hand for the outag No violations or deviations were identifie ,

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! -4-4. Staffing The'NRC inspector reviewed the licensee's functional organization regarding the health physics program to determine compliance with Technical Specification (TS), Section 6.2; and agreement with the commitments in the Final Safety Analysis Report (FSAR), Chapters 12 and 1 The licensee had supplemented the health physics staff with 30 senior-level technicians and 20 junior-level technicians. The NRC inspector expressed concern that the 30 senior-level technicians (4 in dosimetry and 26 for outage operational support) appeared marginal for the refueling outage, since only a few, approximately 10, of the licensee's permanent staff were ANS/ ANSI 3.1-1978 qualified and these individuals had only limited experience with refueling outages. A second concern was the extended period, approximately 8 days, required to test and process an individual for unescorted access into the facility. The licensee stated they would review the number of senior level technicians available and the period of time required to process them for unescorted acces No violations or deviations were identifie . Training and Qualifications The NRC inspector reviewed the training and qualifications of contract senior-level health physics technicians to determine agreement with FSAR, Section 13 commitments, and the requirements of TS, Section 6.3 and 10 CFR 19.1 The NRC inspector performed a review of the contract senior-level technician resumes, the evaluation criteria used by the licensee to establish ANS/ ANSI 3.1-:.978 qualifications, the radiation protection knowledge acceptance test, and site specific training being provided by the license No violations or deviations were identifie . ALARA The NRC inspector reviewed the licensee's ALARA program for agreement with the recommendations of Regulatory Guides (RG) 8.8 and 8.1 The NRC inspector determined that the licensee had set a goal not to exceed approximately 248 person-rem for this refueling outage. ALARA personnel were actively involved in the planning and scheduling for maintenance activities scheduled for the outage with approximately 95 percent of the identified work packages having been reviewed. The ALARA coordinator had not received the construction group preventative maintenance request (PMR) work packages at the time of this inspectio The NRC inspector discussed with licensee representatives the lack of

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t tbse'constructionPMRworkpackagesandtheneedforanALARAreviewof

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them.? The;1icensee stated that they would receive a sufficient ALARA

. review or the work would'not be performed.

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. The licensee had obtained work history files from the Callaway plant and

. . experiences they'had encountered during their first refueling outage and were using.them as guidance for ALARA planning.

I /The NRC inspector reviewed the.following procedures:

HPH 07-001, " Pre and Post Job ALARA. Review," Revision 1, March 4, 1986 HPH 07-002, "ALARA Reviews," Revision 0, July 22, 1986

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'ADM 01-108, " Outage Planning," Revision 2, June 10, 1986

-ADM 03-960, "Use'of Temporary Shielding," Revision 0, September 30, 1985 ADM 03-050, "WCGS ALARA Program," Revision 4, August 26, 198 No violations or deviations were identifie . External Radiation Exposure Control The NRC inspector reviewed the licensee's external radiation exposure control program to. determine compliance with 10 CFR Parts 20.101, 20.102,

-20.~202, and 20.401, and agreement with the commitments made in

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Section 12.5.2.1 of the FSAR.

i The' NRC inspector reviewed procedure HPH 01-035, " Dosimetry in Non-uniform

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Radiation Fields," Revision 1, June 9, 1986, regarding the use and-processing of thermoluminescent dosimeters (TLD) for personnel who will be

! required to make steam generator. entries during the refueling outage and

! the number of TLDs available to support the outage. The licensee had

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available approximately 3500 standard TLDs and 100 gamma-radiation-only finger rings.

h The licensee had increased the staff for record management, whole body 4 counting, and TLD issuance by four senior-level technicians for the

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. outag The NRC inspector reviewed procedure HPH 03-014, " Personnel i . Decontamination," Revision 1, December 23, 1985, which includes the.

. personnel decontamination record the licensee will use to document all I- incidents of personnel contamination and the " Calculation of Dose from Contamination" form that is used to determine the radiation exposure

. assigned an individual from skin contamination incidents.

No violations or deviations were identified.

Internal Radiation Exposure Control

The NRC inspector reviewed the licensee's internal radiation exposure control program, including airborne radioactivity monitoring and h

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-6-respiratory protection, for agreement with commitments in FSAR 1 _ Sections 12.3.4.2 and 12.5, and compliance with the requirements of 10 CFR Part 20.10 The NRO inspector reviewed the quantity of respiratory protective devices the licensee had available, over 600 respirators and 1000 bubble suits, for the outage. The licensee had installed an additional 700 cubic feet per minute breathing air compressor to supplement the existing permanent plant breathing airline system. The NRC inspector noted that the licensee routinely performs whole body counting on individuals prior to issuance of TLDs and upon completion of the work assignment at the site. The licensee had purchased a stand-up fast scan type of whole body counter to supplement the slower chair type counte The licensee.had purchased eight additional particulate air monitors to supplement the original constant air monitors (CAMS). The licensee had experienced difficulty maintaining the CAMS operational. This had been previously identified in NRC Inspection Report 50-482/85-42, and the licensee has been working with the manufacturer to modify the existing system No violations or deviations were identifie . Exit Interview The NRC inspector met with the licensee representatives and the NRC resident-inspector identified in paragraph 1 of this report at the conclusion of the inspection on October 10, 1986. The NRC inspector summarized the scope and results of the inspection.

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